CN106531233B - A kind of reactor fuel assemblies - Google Patents
A kind of reactor fuel assemblies Download PDFInfo
- Publication number
- CN106531233B CN106531233B CN201611249225.6A CN201611249225A CN106531233B CN 106531233 B CN106531233 B CN 106531233B CN 201611249225 A CN201611249225 A CN 201611249225A CN 106531233 B CN106531233 B CN 106531233B
- Authority
- CN
- China
- Prior art keywords
- gripping apparatus
- long rod
- stock
- fuel assemblies
- reactor fuel
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Fee Related
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/33—Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a kind of reactor fuel assemblies, including fuel element and accommodating mechanism, also include the retaining mechanism for being used to be detachably fixed the accommodating mechanism, the retaining mechanism includes stock, long rod sleeve, gripping apparatus, long rod bearing and connecting rod, the through hole passed through for the stock is provided with the gripping apparatus, and the gripping apparatus is fixed on one end of the long rod sleeve, one end of the stock sequentially passes through the long rod sleeve and the gripping apparatus and is connected with the long rod bearing, the one side towards the long rod bearing of the gripping apparatus is provided with least one pin-and-hole, the one side towards the gripping apparatus of the long rod bearing is provided with and the pin-and-hole quantity, sell accordingly position, one end of the connecting rod is connected with the accommodating mechanism, the other end is connected with the stock.The present invention solves the problem of fuel assembly is fixed in high density cooling agent by retaining mechanism, fuel assembly is fixed on reactor core specified location under normal and predicted operation operating mode.
Description
Technical field
The present invention relates to a kind of reactor fuel assemblies, it is adaptable to lead base reactor, belongs to nuclear engineering field.
Background technology
Lead base is piled up in the forth generation nuclear reactor international symposium of Tokyo, Japan in 2002, is proposed as six kinds of masters
Want one of forth generation nuclear power station concept shut-down system.At present, the 4th generation of technology such as nuclear energy system international symposium (Generation IV
International Forum, GIF) propose that lead base heap is expected to turn into first in authoritative assessment report and realize Industrial demonstration and business
Industry application the 4th generation of technology such as nuclear energy system, in the world Russia, European Union, the U.S., Japan, South Korea, China etc. using lead base heap as
One of main study subject is given priority to.
In lead base heap, fuel assembly is in the operating mode ring of extremely complicated (such as irradiation of high temperature, burn into, Flow vibration)
Border, it is necessary to fully ensure that the integrality of structure and effectively export fission heat, particularly metal cooling agent is to cladding materials
Huge buoyancy, the hard neutron energy spectrum of reactor core and universal design of long refulling cycle that burn into metal cooling agent high density is brought,
So that lead base heap is different from traditional fast reactor, need especially to consider and pay close attention on fuel assembly material and structure design, especially
The problem of fuel assembly is fixed in high density liquid metal cooling agent.
The content of the invention
The technical problems to be solved by the invention are to provide one kind and are easy to fixed in high density cooling agent, and dismounting is also convenient for
Efficiently reactor fuel assemblies.
In order to solve the above-mentioned technical problem, the present invention is adopted the following technical scheme that:A kind of reactor fuel assemblies, including combustion
Expect element and the accommodating mechanism for fixed fuel element, in addition to for being detachably fixed the locking machine of the accommodating mechanism
Structure, the retaining mechanism includes stock, long rod sleeve, gripping apparatus, long rod bearing and connecting rod;
The through hole passed through for the stock is provided with the gripping apparatus, and the gripping apparatus is fixed on the one of the long rod sleeve
End, one end of the stock sequentially passes through the long rod sleeve and the gripping apparatus and is connected with the long rod bearing, the gripping apparatus
One side towards the long rod bearing is provided with least one pin-and-hole, the one side towards the gripping apparatus of the long rod bearing be provided with
The pin-and-hole quantity, position are sold accordingly, and one end of the connecting rod is connected with the accommodating mechanism, the other end and the stock
Connection.
Further, the gripping apparatus and the long rod bearing are the cylinder of on-circular cross-section.
Further, the gripping apparatus and the long rod bearing are regular triangular prism voussoir.
Further, the one side of the remote gripping apparatus of the long rod bearing is provided with guiding piece.
Further, the quantity of the pin-and-hole is 3, and in the distribution of positive triangular symmetrical.
Further, the accommodating mechanism includes outer tube and is connected to the operating head at the two ends of the outer tube
And bottom nozzle.
Further, one end of the connecting rod sequentially passes through the bottom nozzle and outer tube and is connected with the operating head.
Further, the outside of the bottom nozzle is provided with pin, and the connecting rod is also through the pin.
Further, be additionally provided with screen work in the outer tube, for positioning the fuel element, the connecting rod also through
The screen work.
Beneficial effects of the present invention are embodied in:
The present invention is by special retaining mechanism, when installing fuel assembly of the present invention, fuel assembly insertion reactor core lower grid plate
Afterwards, component handling facilities drive gripping apparatus to rotate by the long rod sleeve of rotational lock mechanism, gripping apparatus is connected with lower grid plate, are grabbing
After tool rotation, 3 straight pins being connected with long rod bearing are narrowly focused towards 3 cylinder pin holes of gripping apparatus lower surface, due to by lead
Alloy cooling agent buoyancy effect, long rod bearing and straight pin are connected after floating with gripping apparatus, gripping apparatus is not circled round, and complete fuel stack
Part solves the problem of fuel assembly is fixed in high density cooling agent in the fixation of reactor core, makes fuel assembly normal and pre-
Reactor core specified location can be fixed under meter operating condition, and operation is also very easy to during dismounting, it is convenient and swift, with highly dense
The advantages of spending, easily fix.
Brief description of the drawings
Fig. 1 is accommodating mechanism of the present invention and the structural representation of connecting rod.
Fig. 2 is the cross-sectional view of accommodating mechanism of the present invention.
Fig. 3 is the structural representation of retaining mechanism of the present invention.
In accompanying drawing the mark of each part for:1 fuel element, 2 operating heads, 3 outer tubes, 4 bottom nozzles, 5 pins, 6 connecting rods,
7 screen works, 8 stocks, 9 long rod sleeves, 10 gripping apparatus, 11 long rod bearings, 12 pins, 13 pin-and-holes, 14 guiding pieces.
Embodiment
The invention will be further described below in conjunction with the accompanying drawings:
Referring to Fig. 1, Fig. 2 and Fig. 3.
Reactor fuel assemblies of the present invention, including fuel element 1, the accommodating mechanism for fixed fuel element 1, Yi Jiyong
In the retaining mechanism for being detachably fixed the accommodating mechanism, the retaining mechanism includes stock 8, long rod sleeve 9, gripping apparatus 10, length
Rod bearing 11 and connecting rod 6;
The accommodating mechanism includes outer tube 3 and is connected to the operating head 2 and down tube at the two ends of the outer tube 3
Seat 4, the outside of the bottom nozzle 4 is provided with pin 5, is used as in coolant entrance, the outer tube 3 and is additionally provided with screen work 7, for fixed
The position fuel element 1;In the present invention, upper base and operating head 2 are considered as the part of integration, therefore have eliminated pipe
Seat;It is to be fixedly connected and connecting rod is connected with operating head, bottom nozzle and pin, at wherein at least one.
Stock 8 is thin cylindrical rod;Long rod bearing 11 is regular triangular prism voussoir, upper surface and the stock 8 of long rod bearing 11
Lower surface is fixedly connected and keeps coaxial, and the seamed edge immediate vicinity of upper surface 3 of long rod bearing 11 is respectively fixedly connected with 3 cylinders
Pin 12, the lower surface of long rod bearing 11 is fixedly connected with a guiding piece 14;Stock 8 has coaxial long rod sleeve 9 and gripping apparatus 10,
There is the regular triangular prism voussoir of through hole centered on gripping apparatus 10, stock 8 passes through long rod sleeve 9, the central through-hole of gripping apparatus 10 and stock
Bearing 11 is connected, and the upper surface of gripping apparatus 10 is fixedly connected with the lower surface of long rod sleeve 9 and keeps coaxial, the lower surface of gripping apparatus 10
3 cylinder pin holes 13 of triangular distribution are drilled with, the diameter of cylinder pin hole 13 is slightly larger than the diameter of straight pin 12, the lower end of gripping apparatus 10
Face passes through 3 cylinder pin holes 13 and 3 cylinder pin connections.
The fuel assembly of development and design as specified above, the operating procedure of installation and removal is as follows:
(1) install
Component refueling agency is inserted by connecting fuel assembly operating head, control fuel assembly to reactor core lower grid plate;Even
Under the guiding piece effect of the long rod bearing of extension bar lower end retaining mechanism, fuel assembly smoothly inserts lower grid plate hole;Component refueling agency
By 60 ° of the long rod sleeve of the hollow cylinder for the rod locking mechanism that is rotatably connected, drive gripping apparatus to rotate 60 °, make gripping apparatus with lower grid plate
End face is connected;3 straight pins being connected with long rod bearing are now narrowly focused towards 3 cylindrical holes of gripping apparatus lower surface, in metal
Under cooling agent buoyancy, long rod bearing is connected after floating with gripping apparatus, while 3 straight pins are connected with 3 cylindrical holes;Complete combustion
Expect fixation of the component in reactor core lower grid plate.
Lower grid plate can be that tri-angle-holed a, cross section for gripping apparatus has been opened on simple thick sheet metal structure, thick sheet metal
The triangle length of side be slightly less than tri-angle-holed on thick sheet metal, gripping apparatus is moved downward, and makes the regular triangular prism voussoir for having through hole
After below thick sheet metal, voussoir rotates 60 °, and now the three of regular triangular prism voussoir angle can be blocked by thick sheet metal, even if
Buoyancy is more than gravity, and gripping apparatus can not also float.Here the connection on-fixed annexation of gripping apparatus and thick sheet metal lower surface, but
Abutment relation.
(2) dismantle
Component refueling agency overcomes buoyancy by connecting fuel assembly operating head, the control long rod bearing in connecting rod lower end
Move downward, until 3 straight pins are disconnected with 3 cylindrical holes;Component refueling agency passes through the rod locking mechanism that is rotatably connected
60 ° of the long rod sleeve of hollow cylinder, gripping apparatus is disconnected with lower grid plate lower surface;Component refueling agency is by lifting fuel stack
Part, makes fuel assembly leave reactor core lower grid plate hole, and steps up to leaving reactor core.
Non-elaborated part of the present invention belongs to techniques well known.
It is described above, it is only part embodiment of the present invention, but protection scope of the present invention is not limited thereto, times
What those skilled in the art the invention discloses technical scope in, the change or replacement that can be readily occurred in should all be covered
Within protection scope of the present invention.
Claims (9)
1. a kind of reactor fuel assemblies, including fuel element (1) and the accommodating mechanism for fixed fuel element (1), also
Including the retaining mechanism for being detachably fixed the accommodating mechanism, it is characterised in that:The retaining mechanism include stock (8),
Long rod sleeve (9), gripping apparatus (10), long rod bearing (11) and connecting rod (6);
The through hole passed through for the stock (8) is provided with the gripping apparatus (10), and the gripping apparatus (10) is fixed on the stock
One end of sleeve (9), one end of the stock (8) sequentially passes through the long rod sleeve (9) and the gripping apparatus (10) and the length
Rod bearing (11) is connected, and the one side towards the long rod bearing (11) of the gripping apparatus (10) is provided with least one pin-and-hole (13),
The one side towards the gripping apparatus (10) of the long rod bearing (11) is provided with and the pin-and-hole (13) quantity, position is corresponding sells
(12), one end of the connecting rod (6) is connected with the accommodating mechanism, the other end is connected with the stock (8).
2. reactor fuel assemblies as claimed in claim 1, it is characterised in that:The gripping apparatus (10) and the long rod bearing
(11) be on-circular cross-section cylinder.
3. reactor fuel assemblies as claimed in claim 1 or 2, it is characterised in that:The gripping apparatus (10) and the stock branch
Seat (11) is regular triangular prism voussoir.
4. reactor fuel assemblies as claimed in claim 1 or 2, it is characterised in that:The remote institute of the long rod bearing (11)
The one side for stating gripping apparatus (10) is provided with guiding piece (14).
5. reactor fuel assemblies as claimed in claim 1 or 2, it is characterised in that:The quantity of the pin-and-hole (13) is 3,
And in the distribution of positive triangular symmetrical.
6. reactor fuel assemblies as claimed in claim 1 or 2, it is characterised in that:The accommodating mechanism includes outer tube (3)
And it is connected to the operating head (2) and bottom nozzle (4) at the two ends of the outer tube (3).
7. reactor fuel assemblies as claimed in claim 6, it is characterised in that:One end of the connecting rod (6) is sequentially passed through
The bottom nozzle (4) and outer tube (3) are connected with the operating head (2).
8. reactor fuel assemblies as claimed in claim 7, it is characterised in that:The outside of the bottom nozzle (4) is provided with pin
(5), the connecting rod (6) is also through the pin (5).
9. reactor fuel assemblies as claimed in claim 7, it is characterised in that:Screen work is additionally provided with the outer tube (3)
(7), for positioning the fuel element (1), the connecting rod (6) is also through the screen work (7).
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201611249225.6A CN106531233B (en) | 2016-12-29 | 2016-12-29 | A kind of reactor fuel assemblies |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201611249225.6A CN106531233B (en) | 2016-12-29 | 2016-12-29 | A kind of reactor fuel assemblies |
Publications (2)
Publication Number | Publication Date |
---|---|
CN106531233A CN106531233A (en) | 2017-03-22 |
CN106531233B true CN106531233B (en) | 2017-08-25 |
Family
ID=58338564
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201611249225.6A Expired - Fee Related CN106531233B (en) | 2016-12-29 | 2016-12-29 | A kind of reactor fuel assemblies |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN106531233B (en) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU2654531C1 (en) * | 2017-09-29 | 2018-05-21 | Акционерное общество "ТВЭЛ" (АО "ТВЭЛ") | Nuclear reactor fuel assembly |
CN109830315B (en) * | 2019-01-29 | 2022-08-02 | 哈尔滨工程大学 | Expanded nuclear reactor core |
Family Cites Families (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
SE328066B (en) * | 1969-04-21 | 1970-09-07 | Asea Atom Ab | |
CN101271738B (en) * | 2008-04-25 | 2011-11-09 | 上海核工程研究设计院 | Clamping head for fuel rod replacing device |
CN101727993B (en) * | 2008-10-24 | 2012-06-27 | 中国核动力研究设计院 | Quick detachable joint of nuclear fuel assembly |
CN102117668B (en) * | 2009-12-31 | 2014-08-27 | 中国核动力研究设计院 | Reactor core unloading tool |
CN101882474A (en) * | 2010-05-12 | 2010-11-10 | 高新区益腾净水设备研发中心 | Rapid detachable joint |
CN102610286B (en) * | 2012-03-30 | 2015-02-04 | 中国科学院合肥物质科学研究院 | Fuel subassembly fixing device of reloadable liquid heavy metal reactor |
US10124472B2 (en) * | 2012-04-16 | 2018-11-13 | Bwxt Mpower, Inc. | Lower end fitting locknut for nuclear fuel assembly |
CN103077756B (en) * | 2013-01-13 | 2016-02-17 | 中国科学院合肥物质科学研究院 | A kind of refueling machine grip device for liquid heavy metal cools stacks |
CN103985419B (en) * | 2014-06-05 | 2016-08-24 | 中国科学院合肥物质科学研究院 | A kind of fuel assembly locking device of liquid heavy metal reactor |
-
2016
- 2016-12-29 CN CN201611249225.6A patent/CN106531233B/en not_active Expired - Fee Related
Also Published As
Publication number | Publication date |
---|---|
CN106531233A (en) | 2017-03-22 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN106531233B (en) | A kind of reactor fuel assemblies | |
JP5675054B2 (en) | Nuclear fuel bundle | |
Ren et al. | Design and application of a special underwater cutting device for the decommissioning of the first HWRR reactor in China | |
CN213793278U (en) | Target plate on-line replacer | |
Aoto et al. | JSFR design study and R and D progress in the FaCT project | |
Hardy et al. | CANDU fuel performance and development | |
Varghese et al. | En-Masse Coolant Channel Replacement in Indian PHWR | |
Park et al. | KNFC fuel service technology development | |
Isozaki et al. | Upgrade of cooling system heat removal capacity of the experimental fast reactor JOYO | |
Kumar Krovvidi et al. | Experience with Material Combinations for Sliding Applications in PFBR In-Vessel Fuel Handling Machine | |
Narabayashi et al. | Development of internal CRD for next generation BWR | |
Tao et al. | A discussion on the inspection and test technology of the post-irradiation fuel assembly | |
Speight | Drive unit for inspecting nuclear fuel rods | |
Chexal et al. | CHECWORKS TM-An integrated computer program for controlling flow-accelerated corrosion | |
Pashkevicius et al. | RBMK-1500 fuel assemblies repair experience at Ignalina NPP | |
Vijayashree et al. | Design and development of diverse safety rod and its drive mechanism for PFBR | |
Alavi et al. | The advanced carrier bundle-comprehensive irradiation of materials in CANDU power reactors | |
Sivaramakrishnan et al. | Post irradiation examination of Dhruva, TAPS and MAPS fuels | |
Feinroth | The First Refueling of the Shippingport Atomic Power Station | |
Kim et al. | Capsule Development and Utilization for Material Irradiation Tests | |
Ding et al. | Test Reactor Irradiation Fuel Assembly Development in China | |
Boulton | Materials and design interaction in advanced reactors | |
Tatone et al. | Steam generator tube performance: Experience with water-cooled nuclear power reactors during 1982 | |
Gerber | History of the 185-/189-D thermal hydraulics laboratory and its effects on reactor operations at the Hanford Site | |
Pierantoni | Review of fast reactor activities in Italy, April 1978 |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
C06 | Publication | ||
PB01 | Publication | ||
SE01 | Entry into force of request for substantive examination | ||
SE01 | Entry into force of request for substantive examination | ||
GR01 | Patent grant | ||
GR01 | Patent grant | ||
CF01 | Termination of patent right due to non-payment of annual fee | ||
CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20170825 Termination date: 20201229 |